ENDF-201: ENDF/B-VI summary documentation

Analyses of fusion integral benchmark experiments at JAEA/FNS with FENDL-2.1 and other recent nuclear data libraries

“…FENDL-2.1 is a collection of the best evaluation for fusion applications from the world-wide nuclear data libraries, ENDF/B-VI.8 [3], JEFF-3.0 [4], Brond-2.1 [5] and JENDL-3.2 [6], -3.3 [7], Fusion File [8].…”

Production of a pulseable fission-like neutron flux using a monoenergetic 14MeV neutron generator and a depleted uranium reflector

“…238 U is a fissionable material whose neutron-induced fission cross-section is 1.13 b at 14 MeV and drops to approximately 0.53 b at 2 MeV [22]. On average, 4.4 neutrons are produced from each fission induced by 14 MeV neutrons, with a Watt spectrum similar to that for 252 Cf [26].…”

“…To induce inelastic scattering, the typical neutron energy must exceed a threshold of order 1 MeV. Oxygen and carbon are examples requiring thresholds of 6.5 and 4.8 MeV, respectively [22]. Elements such as hydrogen, nitrogen, and chlorine, whose signature mechanism is neutron capture, require a neutron spectrum able to efficiently couple to the sample.…”

Monte Carlo modelling of TRIGA research reactor

“…Several nuclear data evaluations such as ENDF/B-VII (Chadwick et al, 2006), ENDF/B-VI.8 (Rose, 1991), JEFF-3.1 (Koning et al, 2006) and JENDL-3.3 (Shibata et al, 2002) were used in this study in order to identify the source of discrepancies that may appear between measured and calculated results (Plaschy, 2004).…”